GB894228A - Boiling water reactor - Google Patents

Boiling water reactor

Info

Publication number
GB894228A
GB894228A GB33980/59A GB3398059A GB894228A GB 894228 A GB894228 A GB 894228A GB 33980/59 A GB33980/59 A GB 33980/59A GB 3398059 A GB3398059 A GB 3398059A GB 894228 A GB894228 A GB 894228A
Authority
GB
United Kingdom
Prior art keywords
zirconium
plates
channels
fuel elements
fuel
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired
Application number
GB33980/59A
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
US Atomic Energy Commission (AEC)
Original Assignee
US Atomic Energy Commission (AEC)
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by US Atomic Energy Commission (AEC) filed Critical US Atomic Energy Commission (AEC)
Publication of GB894228A publication Critical patent/GB894228A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/06—Sealing-plugs
    • G21C13/073—Closures for reactor-vessels, e.g. rotatable
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24—Promoting flow of the coolant
    • G21C15/26—Promoting flow of the coolant by convection, e.g. using chimneys, using divergent channels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/36—Assemblies of plate-shaped fuel elements or coaxial tubes
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/06—Means for locating or supporting fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

894,228. Nuclear reactors and fuel elements. UNITED STATES ATOMIC ENERGY COMMISSION. Oct. 7, 1959 [Nov. 4, 1958], No. 33980/59. Class 39(4) In a boiling water nuclear reactor comprising a pressure vessel in which vertical channels are defined by thermal nuclear fissionable material and are submerged in a steam forming neutron moderator which also acts as a coolant and flows through the channels, the vertical channels are divergently tapered in the direction of moderator flow. The frictional pressure drop through the channels is thus reduced and a formula is given which shows that this reduction is greatest at an angle of taper of less than 1 degree, for example “ degree to <SP>1</SP>/ 3 degree. As shown in Fig. 1, the pressure vessel comprises a steel tank 91 with stainless steel lining 92, thermally insulated by asbestos 76. A secondary steel tank 105 lines the concrete shielding 74 which is cooled by water tubes 107. The reactor core 95 includes fuel elements 116 supported in channels 117 and is approximately the shape of an inverted right conical section. The majority of the fuel elements are as shown in Fig. 3 comprising a mounting stem 120 with three apertures 122 at the base, four plates 128 disposed between zirconium side plates 124 and so arranged that the spacers 128a taper divergently in an upward direction, and a rectangular discharge fitting 126 having orifices 133. Each plate 128 consists of a body 129 of natural uranium, zirconium, and niobium, covered with zirconium cladding 130. Some of the fuel elements are as shown in Fig. 5 in which the centre part 140b of each of the fuel plates 140 consiists of two plates of an alloy of zirconium and enriched uranium separated by a zirconium spacer. Neutron-absorbing control rods 112 are operated by mechanism 111 and, as shown in Fig. 9, each rod 112 consists of a plate 150 made of cadmium, boron, or gadolinium, clad in stainless steel 151, and slides in a tubular zirconium housing 147. Steam collects above the water level 156 in the reactor and passes through pipe 158 to steam turbine plant arranged as described in Specification 886,874. Condensate returns through pipe 171 and distribution rings 173. A modified core design, Fig. 13 (not shown), comprises a series of shells in the form of right circular conical frustrums, between which fuel plates are arranged radially, the plates increasing in width along their length and also increasing in thickness with distance from the core centre.
GB33980/59A 1958-11-04 1959-10-07 Boiling water reactor Expired GB894228A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US77193158A 1958-11-04 1958-11-04

Publications (1)

Publication Number Publication Date
GB894228A true GB894228A (en) 1962-04-18

Family

ID=38651922

Family Applications (1)

Application Number Title Priority Date Filing Date
GB33980/59A Expired GB894228A (en) 1958-11-04 1959-10-07 Boiling water reactor

Country Status (4)

Country Link
BE (1) BE583982A (en)
DE (1) DE1218077B (en)
FR (1) FR1237542A (en)
GB (1) GB894228A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3398050A (en) * 1966-01-07 1968-08-20 Atomic Power Dev Ass Inc Nuclear reactor system
US3488253A (en) * 1966-01-07 1970-01-06 Atomic Power Dev Ass Inc Nuclear reactor system
US3503849A (en) * 1966-01-07 1970-03-31 Atomic Power Dev Ass Inc Method of replacing subassemblies in nuclear reactors

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3515638A (en) * 1967-05-12 1970-06-02 Atomic Power Dev Ass Inc Fuel systems for nuclear reactors

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE553051A (en) * 1955-11-30
NL113104C (en) * 1956-02-16
DE1027338B (en) * 1956-10-06 1958-04-03 Siemens Ag Nuclear reactor with two pressure zones

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3398050A (en) * 1966-01-07 1968-08-20 Atomic Power Dev Ass Inc Nuclear reactor system
US3488253A (en) * 1966-01-07 1970-01-06 Atomic Power Dev Ass Inc Nuclear reactor system
US3503849A (en) * 1966-01-07 1970-03-31 Atomic Power Dev Ass Inc Method of replacing subassemblies in nuclear reactors

Also Published As

Publication number Publication date
DE1218077B (en) 1966-06-02
BE583982A (en) 1960-02-15
FR1237542A (en) 1960-07-29

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